Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor

Nuclear data consists of measured or evaluated probabilities of various fundamental physical interactions involving the nuclei of atoms and their properties. Most fluoride salt-cooled high-temperature reactor (FHR) studies that were reviewed do not give detailed information on the data libraries use...

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Main Authors: Mohamed H., Lindley B., Parks G.
Other Authors: 57136356100
Format: Conference Paper
Published: American Institute of Physics Inc. 2023
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spelling my.uniten.dspace-233242023-05-29T14:39:30Z Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor Mohamed H. Lindley B. Parks G. 57136356100 49863846400 7103057721 Nuclear data consists of measured or evaluated probabilities of various fundamental physical interactions involving the nuclei of atoms and their properties. Most fluoride salt-cooled high-temperature reactor (FHR) studies that were reviewed do not give detailed information on the data libraries used in their assessments. Therefore, the main objective of this data libraries comparison study is to investigate whether there are any significant discrepancies between main data libraries, namely ENDF/B-VII, JEFF-3.1 and JEF-2.2. Knowing the discrepancies, especially its magnitude, is important and relevant for readers as to whether further cautions are necessary for any future verification or validation processes when modelling an FHR. The study is performed using AMEC's reactor physics software tool, WIMS. The WIMS calculation is simply a 2-D infinite lattice of fuel assembly calculation. The comparison between the data libraries in terms of infinite multiplication factor, kinf and pin power map are presented. Results show that the discrepancy between JEFF-3.1 and ENDF/B-VII libraries is reasonably small but increases as the fuel depletes due to the data libraries uncertainties that are accumulated at each burnup step. Additionally, there are large discrepancies between JEF-2.2 and ENDF/B-VII because of the inadequacy of the JEF-2.2 library. Final 2023-05-29T06:39:30Z 2023-05-29T06:39:30Z 2017 Conference Paper 10.1063/1.4972905 2-s2.0-85031287397 https://www.scopus.com/inward/record.uri?eid=2-s2.0-85031287397&doi=10.1063%2f1.4972905&partnerID=40&md5=801071e9fcd26600733d9c15a440270a https://irepository.uniten.edu.my/handle/123456789/23324 1799 20007 All Open Access, Bronze American Institute of Physics Inc. Scopus
institution Universiti Tenaga Nasional
building UNITEN Library
collection Institutional Repository
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content_provider Universiti Tenaga Nasional
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description Nuclear data consists of measured or evaluated probabilities of various fundamental physical interactions involving the nuclei of atoms and their properties. Most fluoride salt-cooled high-temperature reactor (FHR) studies that were reviewed do not give detailed information on the data libraries used in their assessments. Therefore, the main objective of this data libraries comparison study is to investigate whether there are any significant discrepancies between main data libraries, namely ENDF/B-VII, JEFF-3.1 and JEF-2.2. Knowing the discrepancies, especially its magnitude, is important and relevant for readers as to whether further cautions are necessary for any future verification or validation processes when modelling an FHR. The study is performed using AMEC's reactor physics software tool, WIMS. The WIMS calculation is simply a 2-D infinite lattice of fuel assembly calculation. The comparison between the data libraries in terms of infinite multiplication factor, kinf and pin power map are presented. Results show that the discrepancy between JEFF-3.1 and ENDF/B-VII libraries is reasonably small but increases as the fuel depletes due to the data libraries uncertainties that are accumulated at each burnup step. Additionally, there are large discrepancies between JEF-2.2 and ENDF/B-VII because of the inadequacy of the JEF-2.2 library.
author2 57136356100
author_facet 57136356100
Mohamed H.
Lindley B.
Parks G.
format Conference Paper
author Mohamed H.
Lindley B.
Parks G.
spellingShingle Mohamed H.
Lindley B.
Parks G.
Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
author_sort Mohamed H.
title Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
title_short Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
title_full Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
title_fullStr Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
title_full_unstemmed Nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
title_sort nuclear data libraries assessment for modelling a small fluoride salt-cooled, high-temperature reactor
publisher American Institute of Physics Inc.
publishDate 2023
_version_ 1806423477148712960
score 13.211869